| Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect | |
| Wu, Bin1,2; Ming, Hongliang1,2; Zhang, Zhiming3; Meng, Fanjiang4; He, Guangqing5,6; Wang, Jianqiu1,2,3; Han, En-Hou1,3 | |
| Corresponding Author | Ming, Hongliang(hlming12s@imr.ac.cn) ; Meng, Fanjiang(mengfanjiang@snerdi.com.cn) |
| 2022-05-01 | |
| Source Publication | JOURNAL OF NUCLEAR MATERIALS
 |
| ISSN | 0022-3115 |
| Volume | 563Pages:14 |
| Abstract | S C Alloy 690TT tube samples with different sizes of internal bulge defect (IBD) are prepared by actual hydraulic tube expansion in field and their microstructure and stress corrosion cracking (SCC) behavior are studied in detail. The hardening level and residual strain increase as moving from the original area of the tube to the bulged area, and so as for the increasing of deformation sizes. Corrosion test with a duration of 20 0 0 h shows that the IBD area has higher SCC sensitivity than the original tube. In addition, IBD with larger size is more sensitive to SCC. (c) 2022 Elsevier B.V. All rights reserved. |
| Keyword | Alloy 690TT Tube expansion Internal bulge defect Stress corrosion cracking Intergranular corrosion High temperature corrosion |
| Funding Organization | Youth Innovation Promo-tion Association CAS ; National Natural Science Foun-dation of China ; National Key RD Program ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China) |
| DOI | 10.1016/j.jnucmat.2022.153629 |
| Indexed By | SCI |
| Language | 英语 |
| Funding Project | Youth Innovation Promo-tion Association CAS[2022187] ; National Natural Science Foun-dation of China[51771211] ; National Key RD Program[2019YFB1900904] ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)[2021NMSAKF01] ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)[2022NMSAKF03] |
| WOS Research Area | Materials Science ; Nuclear Science & Technology |
| WOS Subject | Materials Science, Multidisciplinary ; Nuclear Science & Technology |
| WOS ID | WOS:000793200400006 |
| Publisher | ELSEVIER |
| Citation statistics | |
| Document Type | 期刊论文 |
| Identifier | http://ir.imr.ac.cn/handle/321006/173930 |
| Collection | 中国科学院金属研究所 |
| Corresponding Author | Ming, Hongliang; Meng, Fanjiang |
| Affiliation | 1.Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 2.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 3.Inst Corros Sci & Technol, Guangzhou 510530, Peoples R China 4.Shanghai Nucl Engn Res & Design Inst Ltd Co, Shanghai 200233, Peoples R China 5.Fudan Univ, Dept Mat Sci, Shanghai 200433, Peoples R China 6.Shanghai Elect Nucl Power Equipment Co Ltd, Shanghai 201306, Peoples R China |
| Recommended Citation GB/T 7714 | Wu, Bin,Ming, Hongliang,Zhang, Zhiming,et al. Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect[J]. JOURNAL OF NUCLEAR MATERIALS,2022,563:14. |
| APA | Wu, Bin.,Ming, Hongliang.,Zhang, Zhiming.,Meng, Fanjiang.,He, Guangqing.,...&Han, En-Hou.(2022).Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect.JOURNAL OF NUCLEAR MATERIALS,563,14. |
| MLA | Wu, Bin,et al."Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect".JOURNAL OF NUCLEAR MATERIALS 563(2022):14. |
| Files in This Item: | There are no files associated with this item. | |||||
Items in the repository are protected by copyright, with all rights reserved, unless otherwise indicated.
Edit Comment